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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Huang, Qingyu Yu, Yang Zeng, Hui Yang, Hui Zhang, Siyuan Yang, Kunlin Lin, Yuanfeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886410

Among the current mainstream nuclear reactor thermal-hydraulic calculation system analysis softwares (such as RELAP5, TRACE, etc.), different empirical or semi-empirical relationships are employed to calculate two-phase interfacial flow parameters. However, due to the lack of understanding of the physical laws of reactor fluids and the limited experimental data currently, the application scope and accuracy of these methods are relatively limited. As an important paradigm in machine learning methods, ensemble learning has received great attention in numerical prediction tasks in many fields due to its excellent robustness, nonlinear fitting ability and strong interpretability. In this study, three typical ensemble learning methods including random forest, gradient boosting regression tree, and extreme gradient boosting tree are used to build a two-phase interfacial parameter prediction model for rectangular channels. The investigated interfacial parameters include interfacial area concentration, void fraction, bubble velocity, bubble chord length, and bubble frequency. The result reveals that XGBoosting has the best performance in forecasting. In order to further improve the performance of the ensemble learning method and solve the problem of poor generalization ability of the homogeneous-ensemble model, the heterogeneous-ensemble strategy are adopted to combine different types of algorithms to provide a model with stronger scalability and generalization ability for two-phase flow interfacial parameter prediction. The results show that the usage of the heterogeneous-ensemble method can improve the prediction ability of the model to a certain extent, and further ensure the reliability of the data-driven model for the prediction of the two-phase interfacial flow key parameters in the rectangular channel. Copyright © 2022 by ASME.

关键词： Two phase flow

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Research on Imputation Method for Missing Values of Nuclear Power Plants' Operation Data 13

Research on Imputation Method for Missing Values of Nuclear ...

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13th International Conference on Electronics, Communications and Networks, CECNet 2023

作者： Liu, Jie Qi, Xiaodi Wu, Zhiqiang Jiang, Wei Chen, Zhi Jian, Yifan Wen, Juan School of Computer/Software University of South China China Laboratory of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute China

ISBN: (纸本)9781643684802

The collection of nuclear power plants operating data is the basis for subsequent fault diagnosis and obtaining the operating status of nuclear power plants, but equipment failures and external interference will lead to missing operating monitoring data, which will reduce the quality of the data and thus reduce the accuracy of the subsequent analysis results. To solve this problem, this paper utilizes the fact that nuclear power plants have accumulated a large amount of operational data and researches the method of generating adversarial imputation network (GAIN)-based imputation method for missing values of nuclear power plants' operational data. The generator in the model estimates the missing values by learning the distribution of the true values, and the discriminator in the model discriminates which values are true and which are generated with the help of a hint matrix. The hint reveals partial information about the missing original samples to the discriminator, which the discriminator uses to focus its attention on the quality of the imputation of particular data values. Finally, a training set and a test set were constructed for comparative experiments on the PCTran simulation platform by simulating the operational data of the AP1000 as an example. The experimental results demonstrate that the investigated algorithm achieves lower root mean square error (RMSE), verifying the feasibility and accuracy of the method. © 2024 The authors and IOS Press.

关键词： Nuclear power plants

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POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA ORIENTED NUCLEAR reactor ACCIDENT DIAGNOSIS system 29

POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Li, Chengyuan Li, Meifu Qiu, Zhifang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886427

During applying data-oriented diagnosis systems to distinguishing the type of and evaluating the severity of nuclear power plant initial events, it is of vital importance to decide which parameters to be used as the system input. However, although several diagnosis systems have already achieved acceptable performance in diagnosis precision and speed, hardly have the researchers discussed the method of monitoring point choosing and its layout. For this reason, redundant measuring data are used to train the diagnostic model, leading to high uncertainty of the classification, extra training time consumption, and higher probability of overfitting while training. In this study, a method of choosing thermal hydraulics parameters of a nuclear power plant is proposed, using the theory of post-hoc interpretability theory in deep learning. At the start, a novel Time-sequential Residual Convolutional Neural Network (TRES-CNN) diagnosis model is introduced to identify the position and hydrodynamic diameter of breaks in LOCA, using 38 parameters manually chosen on HPR1000 empirically. Afterwards, post-hoc interpretability methods are applied to evaluate the attributions of diagnosis model’s outputs, deciding which 15 parameters to be more decisive in diagnosing LOCA details. The results show that the TRES-CNN based diagnostic model successfully predicts the position and size of breaks in LOCA via selected 15 parameters of HPR1000, with 25% of time consumption while training the model compared the process using total 38 parameters. In addition, the relative diagnostic accuracy error is within 1.5% compared with the model using parameters chosen empirically, which can be regarded as the same amount of diagnostic reliability. Copyright © 2022 by ASME.

关键词： Nuclear power plants

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EMC PERFORMANCE OF DIFFERENT CABLE ROUTING STYLES FOR I&C systemS OF NPPS 29

EMC PERFORMANCE OF DIFFERENT CABLE ROUTING STYLES FOR I&C SY...

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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Yang, Youwei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791886373

In the nuclear power plants, cables are signal transport links between separated signal processes that must be allowed to communicate with one another in a specified manner. Nowadays, for the instrumentation and control system of nuclear power reactor, there have always two ways to place the cables, i.e. above the cabinet or underneath the cabinet. One of the two ways is often preferred on account of the local installation environment or the human factor, while the electromagnetic compatibility (EMC) performance of these two ways is seldom reported. The pitfall may compromise the electromagnetic compatibility performance of the cabinet, or the system or installation it is used in, even when all the components used in the cabinet have excellent EMC compliance individually. In this paper, based on the numerical simulation technology, numerical models were built for the instrumentation and control system with the two different cable routing styles. Radiated emission, radiated susceptibility and crosstalk of cables connected to the cabinets are mainly researched. Results show that the different cable routing styles mainly affect the radiated susceptibility performance and the way that underneath the cabinet is preferred. Copyright © 2022 by ASME.

关键词： Electromagnetic compatibility

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Application of Optimal design in Nuclear Safety-Class DCS design 6th

Application of Optimal Design in Nuclear Safety-Class DCS De...

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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Zhang, Xu Yao, Zhang Chen, Shi-Yong Peng, Hao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811911804

In the design process of nuclear safety-class digital control system (DCS), there may be mistakes in the details of various drawings for the large number of drawings and heavy design task. In safety-class DCS, with the trait of redundancy channel and equipment, cabinets within the same system have high similarity. At the same time, different units also have high similarity. According to the characteristics of these requirements, the deep development of engineering design software has realized a series of functions such as automatic drawing design, content automatic check and drawing automatic conversion. Combining the above design ideas with software automation technology, the design process is optimized, the engineering design efficiency is greatly improved, and the engineering design cycle is shortened. The optimization design method in this paper has been applied to the safety-class DCS design of Unit 1&2 of Zhangzhou nuclear power plant, and has achieved good results. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Digital control systems

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Nuclear Safety-Class DCS Hardware Logic Implementation Scheme Based on Modularization design 6th

Nuclear Safety-Class DCS Hardware Logic Implementation Schem...

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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021

作者： Hu, Yan-Liang Zhang, Xu Chen, Shi-Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789811911804

At present, nuclear safety-class DCS can deal with the common cause failure of digital control system software system by building hardware logic control circuit. Different from the digital control system, the hardware logic control circuit is mainly designed and realized by switches, relays and delay relays, which improves the diversity of the system. However, when the safety-class DCS put into operation, the hardware logic control system fault troubleshooting, regular test and other work is relatively heavy. In order to improve the testability and maintainability of safety-class DCS hardware logic control system, this paper proposes a scheme based on the modular hardware logic design method and the matching hardware logic test device. © 2022, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Digital control systems

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Phase-Field Modelling of Void Evolution in Binary Alloys Under Irradiation

Phase-Field Modelling of Void Evolution in Binary Alloys Und...

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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023

作者： Lu, Yong Yang, Yuhang Li, Wenjie Sun, Dan Liu, Xingjun Wang, Cuiping College of Materials and Fujian Key Laboratory of Surface and Interface Engineering for High Performance Materials Fujian Xiamen China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789819971565

The formation and growth of voids have significant influence on the dimensional changes of nuclear materials subjected to irradiation. In this paper, we developed a phase-field model to investigate the evolution of voids in binary alloys under irradiation, which includes the process of irradiation-induced defect formation and annihilation. The relationship of alloy composition and defect formation energy was determined. The nucleation and growth of voids for various alloy compositions were simulated to investigate the effect of solute composition on the void growth kinetics. Our simulation results indicate that, the composition of matrix phase and its influence on the formation energy of vacancy are essential for the growth kinetics and void distribution during irradiation. As an example, the void nucleation and growth in U-Zr alloys are also studied and consistence between the present results and experimental observations were obtained. © The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd 2024.

关键词： Binary alloys

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Improving the ductility of laser directed energy deposited borated stainless steel by increasing laser power

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Journal of Manufacturing Processes 2025年 145卷 494-507页

作者： Huang, Sheng Li, Qingyu Zhang, Xiaoyu Cui, Bin Li, Dichen Zhang, Anfeng Miao, Kai State Key Laboratory for Manufacturing Systems Engineering School of Mechanical Engineering Xi'an Jiaotong University Xi'an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Department of Mechanical and Electrical Engineering Yuncheng University Yuncheng044000 China Co. Ltd. Chengdu610091 China

Borated stainless steels (BSSs) are extensively applied in the nuclear energy industry due to boron's excellent thermal neutron absorption capacity, but large and brittle borides formed during casting result in a low ductility. Here, a BSS was produced by laser directed energy deposition, and an investigation was conducted to analyze the impact of laser power on both the microstructure and mechanical properties of the deposited material. Fibrous borides with relatively low volume fraction in the overlapping zone resulted in higher ductility, while lamellar borides with relatively large volume fraction in the non-overlapping zone led to higher strength. As the laser power increased from 180 W to 330 W, the size of fibrous and lamellar eutectic borides and austenite increased significantly, the width of the soft overlapping zone increased by 2.27 times, and the elongation increased by 2.03 times, although yield strength and ultimate tensile strength decreased by 46.3 % and 31.7 %, respectively. As a result, these findings confirmed the feasibility of significantly improving the ductility of the as-deposited BSS by increasing the laser power. The work here provides a way to tailoring the mechanical properties of BSS produced by laser additive manufacturing. © 2025 The Society of Manufacturing Engineers

关键词： Ductility

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Experimental Study on Startup Characteristics of Sodium Heat Pipe with Large Length-diameter Ratio 12

Experimental Study on Startup Characteristics of Sodium Heat...

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12th Academic Conference of Geology Resource Management and Sustainable Development, GRMSD 2024

作者： Li, Wenjun Zhang, Zhuohua Su, Dongchuan Wu, Ge Tang, Qizhong Wu, Junjie College of Chemical Safety North China Institute of Science and Technology Hebei Sanhe065201 China Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Research and Design Institute of China Sichuan Chengdu610213 China

ISBN: (纸本)9798331314545

Underground in-situ pyrolysis of oil-rich coal can extract oil and gas resources in coal, which is an important measure for clean and low-carbon utilization of coal resources. The efficiency and energy consumption of underground in-situ pyrolysis of oil-rich coal depend on the heating equipment. The sodium heat pipe with large length-diameter ratio can complete the efficient long-distance heat transfer at high temperature, and has broad application prospects in the field of underground in-situ pyrolysis of oil-rich coal. Compared with the conventional high temperature heat pipe, the evaporation section of the sodium heat pipe with large length-diameter ratio is more likely to burn out during cold start-up, which leads to the failure of cold start-up. Therefore, for the sodium heat pipe with an aspect ratio of 115 (outer diameter D = 20 mm, axial length L = 2300 mm), the start-up characteristics of sodium heat pipes with three filling rates (5 %, 10 %, 15 %) under different heating powers were investigated. The results show that with the increase of the filling rate, the longer the start-up time of the sodium heat pipe with large length-diameter ratio, the more likely it is to produce temperature oscillation. Increasing the heating power can reduce the start-up time gap of the three liquid-filled sodium heat pipes, weaken the temperature oscillation phenomenon, and improve the temperature uniformity and steady-state operating temperature of the sodium heat pipe with large length-diameter ratio. In addition, the decrease of the filling rate of sodium with large length-diameter ratio and the increase of heating power can reduce the equivalent thermal resistance of sodium heat pipe with large length-diameter ratio, and improve the start-up characteristics and heat transfer effect of sodium heat pipe with large length-diameter ratio. When the heating power is 3.5 kW, the start-up time of sodium heat pipe with 5 % filling rate is as low as 450 s. © 2024 Proceedings of the

关键词： Coal deposits

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design of Static Semantic Analyzer for Code Generator Applied in Safety-Level I&C of NPPs 7th

Design of Static Semantic Analyzer for Code Generator Applie...

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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Lan, Lin Wang, Gang Tu, Jun Li, Zhe Huang, Di Zhang, Jia-Cheng Jiang, Wei Nuclear Power Institute of China Institute of Reactor Operation and Application Leshan Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China

ISBN: (纸本)9789819934546

In the nuclear safety level I&C (Instrument and Control) area, the code generator plays an important role in developing the application software. The main function of the code generator is to translate the Lustre program corresponding to the graphical control algorithm into C code. Therefore, the reliability and quality of the code generator will directly affect the safe and reliable operation of nuclear power plants. In order to ensure the correctness of Lustre code, a static semantic analyzer is designed and developed to find the errors in source Lustre code. Its function is to check the correctness of the input source Lustre code, including identifier-checking declarations, identifier-checking programs, type-checking expressions and equations, clock-checking expressions and equations. According to the characteristics of Lustre language, the static semantic analyzer is designed and developed, and its function and correctness are verified by a large number of test cases. In this paper, mainly introducing the design and implementation of the static semantic analyzer. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Semantics

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